The friction characteristics of a full-scale straight-tube model of the ART fuel-to-NaK heat exchanger were determined experimentally. The presence of the spacers resulted in a transition to semi-turbulent flow at a Reynolds modulus of 350. this semi-turbulent flow persisted up to a Reynolds modulus of 5,000. The circumferential spacers were found to contribute slightly more than the radial spacers to the pressure loss in the heat exchanger.

A crucial letter addressing the principal of North Hi Mount Elementary School from the WESTAT Corporation. The document unveils strategic insights and findings as part of the TETAC project report.

A crucial communication where the WESTAT Corporation addresses the principal of E.M. Daggett Middle School, presenting a comprehensive report on the TETAC project.

Data has been previously presented to show that aluminum corrosion in high temperature water may proceed with either a parabolic or a linear dependence on time. The rate of the parabolic process is an Arrhenius function of temperature and essentially independent of alloy composition. More recently several aluminum melts have been tested which corrode by a logarithmic rate process.

The tendency for Austenitic Stainless Steels to develop cracks may be considered to be a function of several variables. Chemical composition of the electrode and base metal, are variables which have been reported to greatly influence the final behavior of the weld. Two types of electrodes, Type 308L and Type 347, were compared with respect to their respective crack sensitivities. Also, comparative results were desired between the 308L-15 (DC) and 308L-15 (AC-DC) type electrodes. At present, no standard test has been designed that will yield quantitative results as to the crack-resistant properties of a weld. With this in mind, the "Arcos Segmented Circular-Groove Notch Sensitivity Test" was chosen as the test to be used, since other investigations have employed the test and some comparison of results could be made.

Technical report: Measurements have been made on the equilibrium between Cu, Cu2+, U4+, and UO22+ in H2SO4 in an attempt to establish the value of the U4+ - UO22+ couple potential. The value of the formal potential for the U3+ - U4+ couple in 1N HCl at 0 degrees C was determined to be + 0.65 v.

The cup assembly of the Experimental Breeder Reactor (EBR) consists of blanket bricks, inner rings, and safety plug, all of natural uranium. The design of the finish machined brick is shown in Figure 1. These pie shaped bricks when stacked together, 12 bricks arranged in circular form and stacked seven rings high, comprise the cylindrical portion of the outer blanket, 17.875" I.D. x 30.875" O.D. after machining and canning. The inner ring, which is shown in Figure 2, fits inside the bottom layer of bricks. The circular opening in the center of the inner ring is closed by the safety plug shown in Figure 3.

From abstract: "The hydrides of group VB an VB elements, except CH4 and NH3, have been prepared and, except for PbH4 and BiH3, their mass spectra studied. Fragmentation patterns and appearance potentials of the positive ions from these hydrides are reported. The ions have been tested for excess kinetic energy and this energy was found to be negligible. The average M-H bond energies and the ΔHf° obtained from appearance potential data agree well with values obtained by other methods. Evidence is cited for the existence of distibine."

This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.

This technical report discusses processes to study the stability constants and intrinsic solubility of several Nickel(II)-vic-Dioxime complexes.

Herman Lurie's weekly report for the sugar market. Details include prices, distribution, sugar tons, and refiners.

In the Tritiated Liquid Waste Decontamination (Molecular Excitation) program, it was found that a 1/4'' Nd:YAG amplifier and a Faraday rotator isolator must be added to the oscillator to obtain the required power for the laser excitation experiments. The isotopic selectivity of the two-photon dissociation process was examined in more detail. The selectivity or ratio of HTO to H/sub 2/O molecules that are photodissociated was found to be on the order of 25, which is inadequate for application to large-scale detritiation projects, e.g., nuclear fuel reprocessing plant waste. The selectivity is such that most of the laser energy is wasted in photodissociation of H/sub 2/O. This obstacle may be overcome by pumping more vibrational energy into the HTO molecules. Various schemes towards this end are being considered. Extensive ab initio calculations on the potential surface for the hydrogen atom-water exchange reaction have been carried out. The energy barrier is calculated to be 38 1/2 kcal/mole, which implies that the exchange reaction T + H/sub 2/O ..-->.. HTO + H is at least 10/sup 9/ times slower than the exchange reaction T + H/sub 2/ ..-->.. HT + H. Calculations were also performed on the analogous hydrogen atom-hydrogen fluoride exchange reaction. …

In 1975 the National Neutron Cross Section Center (NNCSC) at BNL was asked to carry out a study of the nuclear structure and charged-particle reaction data compilation and evaluation efforts in the U. S. with a view toward establishing at NNCSC responsibility for a fully coordinated effort involving measurers, compilers, evaluators, and users whose activities would result in the creation and maintenance of a master file for nuclear structure and charged-particle reaction data. A critique of this study was made by the Ad Hoc Panel on Basic Nuclear Data Compilations; this critique is presented here. The Panel recommended the establishment of a standing panel to monitor and advise on the implementation of the proposed new organizational arrangement for carrying out basic data compilations. (RWR)

Weekly report of the Texas Crop and Livestock Reporting Service on turkey poult numbers in Texas and compared with other states. It includes compiled statistics across six consecutive weeks during two years for turkey eggs set and poults hatched.

This two-dimensional photoelastic study was performed as a means of determining what effect a notch at the base of the flanges had on the strength of these parts. These notches were proposed as a means of clamping the shield and reflectors. The objective of this test was to determine the amount of increased stress in the flange and clamp at the required locations.

This analysis was undertaken to assess the merit of directly supplying certain residence loads with the DC power available from he solar array/battery power sources rather than inverting the power to AC with losses resulting from inverter inefficiency.

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Seventy five percent of natural latex rubber gloves used in laboratories at the Savannah River Site are not reused. A cost analysis performed by the SRS Procurement Department determined that a net savings of $1,092,210 could be achieved annually by recycling latex rubber gloves. The Materials Technology Section, at the request of the Procurement Department, examined some mechanical and chemical properties of latex rubber gloves manufactured by Ansell Edmont, which had been purchased by the site specifications for protective clothing. It also examined mechanical properties of re-cycled gloves purchased by specifications and of {open_quotes}off the shelf{close_quotes} gloves manufactured by North Brothers Company. Finally, water vapor transmission studies, simulating tritium permeation, were performed on gloves from both manufacturers. These studies were performed to determine whether latex rubber gloves can be recycled or whether using only new, unwashed gloves is required in areas where tritium exposure is a possibility. The results of these studies indicate that the acceptable glove characteristics, required in the WSRC Manual 5Q1.11, Protective Clothing Specifications, are not adversely affected after washing and drying the gloves manufactured by Ansell Edmont for seven cycles. Results also indicate that natural latex rubber gloves manufactured by North Brothers comply with most of …

The purpose of this study is to determine whether changes to Hanford operations, as well as changes in the regulatory environment, will require new approaches to ensure radiation protection of the public and the environment. This document discusses the applicable regulations that govern public radiation protection at DOE facilities, recent radiological assessments for members of the public near the Hanford Site, and possible new approaches that may be needed to assure that the Hanford Site can demonstrate compliance with regulatory requirements for radiological protection of the public.

The graphite movement which has occurred at the various reactors has been characterized by two problems: (1) Crooked channels and (2) cracks and miscellaneous voids where pieces of blocks are missing. Of these problems, the cracks and voids have been the most serious in the case of ball drops. Alleviation of the crooked channels can sometimes be accomplished by graphite removal methods such as broaching, but unless some method is found to prevent the balls from entering cracks, the total effect of a ball drop would still be intolerable. Of the two methods of closing the cracks, a paste caulking procedure is anticipated to be less expensive than sleeving, both in terms of cost of the operation and the number of process tube channels which might be lost. If the VSR channel does not require drastic straightening or entry of large tooling, satisfactory caulking can be done without removal of the step plug. ``Poison`` chain may be considered as an alternative to caulking or sleeving for those outer VSR channels where the sole use of balls is for ``total control`` rather than ``speed of control.`` The objectives of this test are (1) to authorize the experimental crack filling of one …

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The objective of Production Test IP-725 was to investigate the reaction rate between graphite and carbon dioxide in F Reactor at a temperature 50 C higher than that currently permitted by Process Standards. After approval of the test, the temperature limit was increased from 650 to 700 C. After approximately three weeks of operation with the-higher temperature limit, the reactor was shut down and the graphite oxidation monitor samples which had been inserted for this test were discharged and measured. It is believed that sufficient data have row been obtained from the first phase of the test to warrant investigation at an even higher temperatures. It is therefore the objective of the supplement described in this report to raise the graphite temperature limit at F Reactor by an additional 50 C to a limit of 750 C.

A Task Force was established in the Irradiation Processing Department to examine the K-Reactor Water Plant to (1) review the operating and maintenance experience with the water plant as improved since startup, (2) identify major plant additions which could further improve reliability, and (3) estimate the costs of any such additions. The K-Water Plant basically consists of the electrically driven primary cooling system with power supplied by the BPA system, electrically driven secondary or backup cooling system powered by a steam driven emergency generator pair, and a ``last ditch`` system consisting of hydraulic cross-ties between the two K-Water Plants. This report summarizes information developed in the course of the Task Force deliberations.

The existing Hanford production reactors are enveloped by a graphite reflector, a cast iron thermal shield, and a biological shield consisting either of laminations of iron and masonite or of high density concrete. Cooling tubes were bonded into grooves in the cast iron thermal shield blocks with lead. As the graphite moderator continues to contract as a function of exposure, it is felt that the bond between the cooling tubes and the top cast iron blocks will be broken since these blocks are supported by the graphite. In the limit, the cooling tubes undoubtedly will pull from the grooves and be suspended between the cast iron and the top biological shield. In this event the effectiveness of the cooling system will be impaired severely, yet it will be necessary to limit the maximum temperature in (and the temperature gradient through) the top biological shield to assure its integrity. The calculations reported herein were made to provide heat generation rates in the shield complex as a function of fringe poison so that temperature distributions could be calculated for various postulated conditions of the cooling system. Thus, it should be possible to estimate the potential for controlling shield temperatures with fringe poison …